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kw.\*:("Uranio Carburo")

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Results 1 to 25 of 67

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Oxidation behavior of carbide fuelsIYER, V. S; MUKERJEE, S. K; KAMAT, R. V et al.Nuclear technology. 1990, Vol 91, Num 3, pp 388-393, issn 0029-5450Article

Fission product precipitates in irradiated uranium carbonitride fuelKLEYKAMP, H.Journal of nuclear materials. 2002, Vol 300, Num 2-3, pp 273-276, issn 0022-3115Article

Kinetics and mechanism of UO2+C reaction for UC/UC2 preparationMUKERJEE, S. K; DEHADRAYA, J. V; VAIDYA, V. N et al.Journal of nuclear materials. 1994, Vol 210, Num 1-2, pp 107-114, issn 0022-3115Article

The oxidation of uranium monocarbide microspheresMUKERJEE, S. K; RAMA RAO, G. A; DEHADRAYA, J. V et al.Journal of nuclear materials. 1994, Vol 210, Num 1-2, pp 97-106, issn 0022-3115Article

Hybrid thermionic space reactors for power and propulsionSAHIN, S; KENNEL, E. B.Nuclear technology. 1994, Vol 107, Num 2, pp 155-181, issn 0029-5450Article

Evaluation of phases in Pu-C-O and (U,Pu)-C-O systems by X-ray diffractometry and chemical analysisJAIN, G. C; GANGULY, C.Journal of nuclear materials. 1993, Vol 207, pp 169-176, issn 0022-3115Article

Ceramic fuel development for space reactorsMATTHEWS, R. B.American Ceramic Society bulletin. 1992, Vol 71, Num 1, pp 96-101, issn 0002-7812Article

Fuel fabrication processes, design and experimental conditions for the joint US-Swiss mixed carbide test in FFTF (AC-3 test)STRATTON, R. W; LEDERGERBER, G; INGOLD, F et al.Journal of nuclear materials. 1993, Vol 204, pp 39-49, issn 0022-3115Conference Paper

Thermofluid-neutronic stability of the rotating, fluidized bed, space-power reactorLEE, C. C; JONES, O. C; BECKER, M et al.Nuclear engineering and design. 1993, Vol 139, Num 1, pp 17-30, issn 0029-5493Article

Calculation on the energy transition coefficient by up-conversion emission intensity ratioCHENGGUO MING; FENG SONG; YIN YU et al.Journal of alloys and compounds. 2010, Vol 506, Num 1, pp 33-35, issn 0925-8388, 3 p.Article

Processing and fabrication of mixed uranium/refractory metal carbide fuels with liquid-phase sinteringKNIGHT, Travis W; ANGHAIE, Samim.Journal of nuclear materials. 2002, Vol 306, Num 1, pp 54-60, issn 0022-3115Article

Thermal stress analyses of the multilayered fuel particles of a particles-bed reactorDOBRANICH, D; EL-GENK, M. S.Nuclear technology. 1991, Vol 94, Num 3, pp 372-382, issn 0029-5450Article

Le nucléaire à la conquête de l'espace = Nuclear power conquering spaceTechnologies France (Strasbourg). 1996, Num 29, pp 21-23, issn 1257-2489, 5 p.Article

Status of fuel, blanket, and absorber testing in the fast flux test facilityBAKER, R. B; BARD, F. E; LEGGETT, R. D et al.Journal of nuclear materials. 1993, Vol 204, pp 109-118, issn 0022-3115Conference Paper

Studies on the restructuring of fast breeder test reactor fuel by out-of-pile simulationANTONY, M. P; DANIEL, J; MATHEWS, C. K et al.Nuclear technology. 1997, Vol 117, Num 3, pp 299-305, issn 0029-5450Article

Fabrication of (Pu0.55U0.45)C fuel pellets for the second core of the fast breeder test reactor in IndiaCHAITANYAMOY GANGULY; PARAMESHWAR VENKAPPA HEGDE; GYAN CHAND JAIN et al.Nuclear technology. 1994, Vol 105, Num 3, pp 346-354, issn 0029-5450Article

Design study of a power-producing muon catalyzed fusion-fission hybrid reactorKATAOKA, K; YAMASAKI, T; OKA, Y et al.Fusion engineering and design. 1992, Vol 19, Num 1, pp 111-118, issn 0920-3796Article

Behavior of HTGR coated fuel particles in high-temperature testsCHERNIKOV, A. S; LYUTIKOV, R. A; KURBAKOV, S. D et al.Energy (Oxford). 1991, Vol 16, Num 1-2, pp 295-308, issn 0360-5442Article

Crystal structure of ternary compounds C3Fe2U2 and C5Fe2U3ALEKSEEVA, Z. M.Soviet physics. Crystallography. 1990, Vol 35, Num 5, pp 749-750, issn 0038-5638Article

High pressure X-ray diffraction study of UC2 using synchrotron radiationDANCAUSSE, J.-P; HEATHMAN, S; BENEDICT, U et al.Journal of alloys and compounds. 1993, Vol 191, Num 2, pp 309-312, issn 0925-8388Article

History of fast reactor fuel developmentKITTEL, J. H; FROST, B. R. T; MUSTELIER, J. P et al.Journal of nuclear materials. 1993, Vol 204, pp 1-13, issn 0022-3115Conference Paper

Physical and chemical analysis of interaction between oxide fuel and pyrocarbon coating of coated particlesLYUTIKOV, R. A; KROMOV, YU. F; CHERNIKOV, A. S et al.Energy (Oxford). 1991, Vol 16, Num 1-2, pp 501-506, issn 0360-5442Article

Simultaneous determination of uranium carbide dissolution products by capillary zone electrophoresisSLADKOV, Vladimir; FOUREST, Blandine.Journal of chromatography. 2009, Vol 1216, Num 12, pp 2605-2608, issn 0021-9673, 4 p.Article

Stabilities of ternary carbides UWC1.75 and UWC2ANANTHASIVAN, K; KALIAPPAN, I; ANTHONYSAMY, S et al.High-temperature materials and processes. 1997, Vol 16, Num 4, pp 255-260, issn 0334-6455Article

Evolution of HTGR coated particle fuel designSTANSFIELD, O. M.Energy (Oxford). 1991, Vol 16, Num 1-2, pp 33-45, issn 0360-5442Article

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